Means for sustaining a nuclear fission chain reaction



June 18, 1957 E. c. cREUTz ErAL MEANS FOR SUSTAINING A NUCLEAR FISSION CHAIN REACTION Filed Oct. 8. 1946 MEANS FOR SUSTAINING A NUCLEAR FISSHN CHAIN REHN Edward C. Creutz, Pittsburgh, Pa., Leo A. Ghlinger, Los Angeles, Calif., Eugene P. Wigner, Princeton, N. J., and Gale Ii. Young, Hawthorne, N. Y., assigne-rs to the United States of America as represented by the United States Atomic Energy Commission Application October 8, 1945, Serial No. '701,904

1 Claim. (Cl. 24M- 193) This invention relates to the general subject of nuclear fission and more particularly to a novel method and means for sustaining a nuclear fission chain reaction in a system wherein the reactive composition is at least partially liquid and is preferably under pressure.

In a neutronic reactor, a neutron fissionable isotope such as U233, U235, or 94239 or mixtures thereof is subjected to fission by absorption of neutrons, and a selfsustaining chain reaction is established by the neutrons evolved by the fission. In general such reactors comprise bodies of composition containing such fissionable material, for example, natural uranium disposed in a neutron slowing material which slows the neutrons to thermal energies at which they are most eiiicient to produce fission. Such a slowing material is termed a neutron moderator and is preferably formed of a substance having the characteristics of relatively small neutron capture cross section and relatively great scattering cross section. Heat evolved during the reaction is generally removed by passage of a coolant through the reactor in heat exchange relationship therewith by converting the heat to mechanical energy through the use of a heat engine such as a steam turbine. Specific details of the theory and essential characteristics of such reactors are set forth in copending application of Enrico Fermi and Leo Szilard, Serial Number 568,904, filed December 19, 1944, now Patent No. 2,708,656.

In neutronic reactors, the ratio of the fast neutrons produced in one generation by the fissions to the original number of fast neutrons in a theoretical system of infinite size where there can be no external loss of neutrons is called the reproduction or multiplication factor or constant of the system, and is denoted by the symbol K. For any nite system, some neutrons will escape from the periphery of the system. Consequently a system of finite size may be said to have a K constant, even though the value thereof would only exist it' the system as built were extended to infinity without change of geometry or materials. Thus when K is referred to herein as a constant of a system of practical size, it always refers to what would exist in the same type of system of infinite size. If K can be made sufiiciently greater than unity to indicate a net gain in neutrons in the theoretical system of infinite size, and then an actual system is built to be sufficiently large so that this gain is not entirely lost by leakage from the exterior surface of the system, then a selfsustaining chain reacting system of finite and practical size can be built to produce power and related by-products by nuclear fission of natural uranium. The neutron reproduction ratio in a system of finite size therefore, differs from K by the external leakage factor, and by a factor due to the neutron absorption by localized neutron absorber, and the reproduction ratio rnust still be suiiiciently greater than unity to permit the neutron density to rise exponentially with time in the system as built.

During the interchange of neutrons in a system of nite size, comprising bodies of any size disposed in a fr, l l j neutron moderator, neutrons may be lost to the chain reaction in four ways:

1. by absorption or capture in the uranium content of the bodies without producing fission,

2. by absorption or capture in the moderator material itself,

3. by absorption or capture by the impurities present in both the uranium bodies and the moderator,

4. by leakage out of the system through the periphery thereof, which can be reduced by an efficient reflector surrounding the reactive composition.

As stated, the present invention relates to a neutronic reaction system wherein the reactive composition is at least partially liquid and is preferably a structure wherein members containing fissionable material are supported within a liquid neutron moderator, such as heavy water (D20) or ordinary Water. The invention may also be applied to reactors wherein the fissionable material is dissolved in a liquid neutron moderator as, for example, solutions of UO2F2 and UO2SO4 in heavy water; or wherein the ssionable material is suspended within the: liquid moderator to form a colloid or slurry.

The general object of the invention is to provide a; novel neutron reflector of neutron moderator or scatter-- ing material around a liquid or semi-liquid reactive com-- position, said reflector minimizing escape of neutrons'. from the chain reaction, as is more fully discussed in the above-mentioned copending application. By thus reducing neutron losses, a relatively compact active portion of the reactor may be designed which is operative to develop a nuclear fission chain reaction even though said portion is smaller than the critical size at which a reaction would otherwise be sustained. It will be understood that by such a construction considerable quantities of valuable material may be conserved.

Another object of the invention is to arrange a solid neutron reflector within a reaction tank or chamber containing the reactive composition which thus contacts the reflector, thereby eliminating the necessity for aneutron absorbent liner between the reflector and the reactive composition which greatly increases the neutron' refiecting eiciency of the reflector.

Still another object of the invention is to provide an unlined container of solid neutron reflecting or moderating material, said container enclosing a reactive composition such as above described.

Still another object of the invention is to design a structure such as above described wherein an external pressure vessel or container surrounds the reflector structure for resisting operating pressures to which the reactive composition is usually subjected for the purposes hereinafter set forth in detail.

The foregoing and other objects and advantages of the invention will become apparent from the following de scription and the accompanying drawing, which is a diagrammatic vertical sectional view through a neutronic reactor constructed in accordance with the invention.

Describing the invention in detail, it is illustrated as applied to a reactive composition disposed within a reactor tank or chamber 2. preferably formed of a material having the characteristics of relatively great strength such as, for example, stainless steel. The reactive composition comprises a body of neutron moderator liquid 4 and a plurality of aluminum sheathed uranium rods 6 supported from a lead cover 8 on the reactor tank 2. A control rod itl of neutron absorbent material, such as cadmium, is supported within the tank 2, and is adapted to be raised or lowered therein by actuating means (not shown) for the purpose of controlling the neutron density within the system, as is more fully discussed in the above-mentioned copending application.

The reactive composition comprising the moderator 4 and the sheathed uranium rods6 is disposed Within a neutron reflector 12 in the form of an unlined container with a wall thickness of 4 to 6 inches, for example, generally cup-shaped in form and disposed within the tank 2 inabutment with ,the inner surface thereof. The reflector 12 is preferably `formed of 'blocks of solid moderator material such as beryllium or .beryllium oxide, but if desired the rellector may be in 'the form ofv a-.u'nitary container, such as, for example, a casting-or welded structure of substantially pureV beryllium metal. 'It will be understood that the above-described,structure'isnovel in that noliner or tank wall is needed'between reector 12 and the liquid moderator which `directly contactsthe reflector, thereby .dispensing with the neutron absorption of the eliminated lining material, which is customarily a material such as aluminum, capable of absorbing .a smallbut substantial amount of neutrons. A reecting layer could be provided by Yextending the .moderaton such as Dz'O, a distance beyond the rods on all v.-s'ides land the bottoms. However, by providing .the reector 12 within the reactor vtank 2, a relatively large quantity of heavy water 4 is displaced, thereby making ,possible the chain reaction with a .considerably smaller amount of heavy water than would be required if thesolid reflecting material 12 Vwere eliminated and the space Yoccupied `thereby were filled with heavy water.

,Surrounding the tank 2 is a pressure chamber or vault 14, preferably formed of a good radiation shielding material, such as concrete, adapted to absorb substantially all emanations from the reactive composition. The top of the vault 14 is closed by a biological shield or cover 16 adapted to absorb radiation from the reactor,

such shield being preferably composed of alternate layers of iron and masonite and being aiorded Vsupport by crossed I-beams 17.

The moderator liquid 4 is circulated through `the tank 2 by a system (not shown), such as is more fully described in said copending application; and helium under pressure is circulated through the top of tank v2 above the level of the moderator 4 by means of helium inlet and outlet pipes 20 and 22, respectively, said-helium functioning to sweep decomposition gases (D2 and O2) and gaseous fission products from the tank 2. Also, the charge of pressure helium on the heavy Water within the tank 2 is effective to raise the boilingpoint of the heavy water, thereby permitting operation of the reactor at relatively high temperatures without boiling the liquid neutron moderator.

Even -when ordinary water is used `as the moderator, the :internal reflector has numerous advantages. Light water (H2O) While being a good neutron scattering substance due to its hydrogen content, yalso is a good neutron absorber. Beryllium or its oxide, makes a -better reector than the light water and lthus when 4used-,as an internal rellector increases the-efciencyv4of the reactor.

v Furthermore, the internal reector may be used with slurries or solutions, provided care is taken that no cracks or crevices extend into'the reflecting layer wherein uranium particles may lodge to become by continuous neutron bombardment and fission excessively radioactive, and thereby to rise in temperature. A beryllium metal layer with a smooth internal surface is an excellent rellectorfor aneutronic composition comprising a liquid slurry or solutionof issionabley isotopes.

While many .liquid reactive compositions may be .operated under substantial pressures, requiring the use of a stainless steel tank Yback of the reflecting layer, it is to be. noted that for lower Vpressures no backing tank is needed and that the reflecting layer `12 when made to be liquid tight may serve as the sole container for -tlle reactive composition.

From the foregoing it will Vbe understood that the invention comprehends a novel method and means for reducing the .size at which-a neutronic -reactor,`at least partially liquid in form,.is capable of sustainingsanuclear ssion chain reaction, by Aproviding -an unlined :solid reflector around the Vreacting compositionin direct contact therewith.

While the theory of nuclear Vlission set forth herein is based -on theV best presently known experimental data, facts later discovered may modify the theory disclosed. It will be understood thatfvarious embodiments of the invention will'be .apparent to those lskilled lin the art Without departing from the scope ofthe invention v'which is klimited solely by the appended claim.

What is claimed is:

Y vIn a system of the class described, a steel container, a liner of a material selected from the Igroup consisting Aof beryllium oxide and beryllium metal within said container, heavy water moderator within and in contact with said liner and uranium fuel rods disposed in said heavy water moderator, said liner, heavy water moderator and uranium fuel rods cooperating to sustain a nuclear chain reaction.

References Cited in the le of this patent UNITED STATES PATENTS 2,708,656 Fermi et al. May 17, 1955 FOREIGN PATENTS 114,150 Australia May 2, 1940 V114,151 Australia May'3, 1940 233,011 Switzerland Oct. 2, 1944 861,390 France Oct. 28, 1940 OTHER VREFERENCES Nucleonics, June 1953, pages 23, 24. Y A General Account of the Development jot-Methods of Using Atomic Energy for vMilitary Purposes, 1940 1945, by H. D. Smyth, August 1945, pages 42, 43, 75, 106, 107 and 108, 153, 177-180.

Handbook of Chemistry and Physics, `Chemical Rubber Co., 26th ed.V (1942), pages 346, 347.

v Kelly et al.: Phy. Rev. 73, 1135-9 l(1948). 

